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1.发明申请公开(公告)号：US20200075181A1
公开(公告)日：2020-03-05
申请号：US16677904
申请日：2019-11-08
发明人： Min Young CHOI , Yong Kyoon MOK , Yoon Ho KIM , Yeon Soo NA , Chung Yong LEE , Hun JANG , Tae Sik JUNG , Dae Gyun GO , Sung Yong LEE , Seung Jae LEE , Jae Ik KIM
摘要： A zirconium alloy is manufactured through melting; solution heat treatment at 1,000 to 1,050° C. (β) for 30 to 40 min and β-quenching using water; preheating at 630 to 650° C. for 20 to 30 min and hot rolling at a reduction ratio of 60 to 65%; primary intermediate vacuum annealing at 570 to 590° C. for 3 to 4 hr and primarily cold-rolled at a reduction ratio of 30 to 40%; secondary intermediate vacuum annealing at 560 to 580° C. for 2 to 3 hr and secondarily cold-rolled at a reduction ratio of 50 to 60%; tertiary intermediate vacuum annealing at 560 to 580° C. for 2 to 3 hr and tertiarily cold-rolled at a reduction ratio of 30 to 40%; and final vacuum annealing at 460 to 590° C. for 7 to 9 hr.
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公开(公告)号：US20180105915A1
公开(公告)日：2018-04-19
申请号：US15538798
申请日：2016-01-29
发明人： Yong Kyoon MOK , Yoon Ho KIM , Tae Sik JUNG , Sung Yong LEE , Hun JANG , Chung Yong LEE , Yeon Soo NA , Min Young CHOI , Dae Gyun KO , Seung Jae LEE , Jae Ik KIM
摘要： Disclosed is a method of manufacturing a zirconium alloy plate, wherein fine precipitates having an average size of 35 nm or less are uniformly distributed in a matrix through multi-pass hot rolling, thus increasing corrosion resistance and fatigue failure resistance, the method including forming a zirconium alloy ingot (step 1); subjecting the ingot of step 1 to beta annealing and rapid cooling (step 2); preheating the ingot of step 2 (step 3); forming a multi-pass hot-rolled plate through primary hot rolling and then air cooling during which secondary hot rolling is subsequently conducted (step 4); subjecting the multi-pass hot-rolled plate of step 4 to primary intermediate annealing and primary cold rolling (step 5); subjecting the rolled plate of step 5 to secondary intermediate annealing and secondary cold rolling (step 6); subjecting the rolled plate of step 6 to tertiary intermediate annealing and tertiary cold rolling (step 7); and finally annealing the rolled plate of step 7 (step 8).
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3.发明申请ZIRCONIUM ALLOY HAVING EXCELLENT CORROSION RESISTANCE FOR NUCLEAR FUEL CLADDING TUBE AND METHOD OF MANUFACTURING THE SAME 审中-公开具有优异耐腐蚀性的核燃料密封管的锆合金及其制造方法公开(公告)号：US20160307651A1
公开(公告)日：2016-10-20
申请号：US15097341
申请日：2016-04-13
发明人： Min Young CHOI , Yong Kyoon MOK , Yoon Ho KIM , Yeon Soo NA , Chung Yong LEE , Hun JANG , Tae Sik JUNG , Dae Gyun GO , Sung Yong LEE , Seung Jae LEE , Jae Ik KIM
摘要： A zirconium alloy is manufactured through melting; solution heat treatment at 1,000 to 1,050° C. (β) for 30 to 40 min and β-quenching using water; preheating at 630 to 650° C. for 20 to 30 min and hot rolling at a reduction ratio of 60 to 65%; primary intermediate vacuum annealing at 570 to 590° C. for 3 to 4 hr and primarily cold-rolled at a reduction ratio of 30 to 40%; secondary intermediate vacuum annealing at 560 to 580° C. for 2 to 3 hr and secondarily cold-rolled at a reduction ratio of 50 to 60%; tertiary intermediate vacuum annealing at 560 to 580° C. for 2 to 3 hr and tertiarily cold-rolled at a reduction ratio of 30 to 40%; and final vacuum annealing at 460 to 590° C. for 7 to 9 hr.
摘要翻译： 通过熔化制造锆合金; （β）30〜40分钟的固溶热处理，使用水进行β淬火; 在630〜650℃预热20〜30分钟，以60〜65％的压缩率热轧; 在570〜590℃进行3〜4小时的初级中间真空退火，主要以30〜40％的压下率冷轧; 二次中间真空退火在560至580℃下进行2至3小时，然后以50至60％的压缩比二次冷轧; 在560〜580℃下进行3〜3小时的三级中间真空退火，并以30〜40％的压缩比进行三次冷轧; 并在460〜590℃进行最终真空退火7〜9小时。
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4.发明申请公开(公告)号：US20170249998A1
公开(公告)日：2017-08-31
申请号：US15277270
申请日：2016-09-27
发明人： Min Young CHOI , Kwang Young LIM , Seung Jae LEE , Yeon Soo NA , Tae Sik JUNG , Jae Ik KIM , Yong Kyoon MOK , Yoon Ho KIM , Chung Yong LEE , Hun JANG , Dae Gyun GO , Sung Yong LEE , Jong Sung YOO
摘要： This invention relates to a composition and method for manufacturing a large-grained uranium oxide nuclear fuel pellet containing an additive. The nuclear fuel pellet is configured such that a uranium oxide powder and an additive powder composed of an Mg compound and a Si compound or Ca compound and a Al compound are mixed together, thus increasing a grain size to thus suppress the release of fission products, thereby increasing the stability of nuclear fuel, preventing cladding tubes from breaking, and contributing to the stable operation of nuclear power plants, ultimately increasing the overall stability of nuclear power plants including nuclear fuel.
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5.发明申请ZIRCONIUM ALLOY HAVING EXCELLENT CORROSION RESISTANCE AND CREEP RESISTANCE AND METHOD OF MANUFACTURING THE SAME 审中-公开具有优异的耐腐蚀性和耐腐蚀性的ZIRCONIUM合金及其制造方法公开(公告)号：US20160304991A1
公开(公告)日：2016-10-20
申请号：US15097354
申请日：2016-04-13
发明人： Min Young CHOI , Yong Kyoon MOK , Yoon Ho KIM , Yeon Soo NA , Chung Yong LEE , Tae Sik JUNG , Dae Gyun GO , Seung Jae LEE , Jae Ik KIM
摘要： A zirconium alloy is manufactured through melting; solution heat treatment at 1,000 to 1,050° C. for 30 to 40 min and β-quenching using water; preheating at 630 to 650° C. for 20 to 30 min and hot rolling at a reduction ratio of 60 to 65%; primary intermediate vacuum annealing at 570 to 590° C. for 3 to 4 hr and primarily cold-rolled at a reduction ratio of 30 to 40%; secondary intermediate vacuum annealing at 560 to 580° C. for 2 to 3 hr and secondarily cold-rolled at a reduction ratio of 50 to 60%; tertiary intermediate vacuum annealing at 560 to 580° C. for 2 to 3 hr and tertiarily cold-rolled at a reduction ratio of 30 to 40%; and final vacuum annealing at 440 to 650° C. for 7 to 9 hr.
摘要翻译： 通过熔化制造锆合金; 在1000至1050℃下进行30至40分钟的固溶热处理，并使用水淬火; 在630〜650℃预热20〜30分钟，以60〜65％的压缩率热轧; 在570〜590℃进行3〜4小时的初级中间真空退火，主要以30〜40％的压下率冷轧; 二次中间真空退火在560至580℃下进行2至3小时，然后以50至60％的压缩比二次冷轧; 在560〜580℃下进行3〜3小时的三级中间真空退火，并以30〜40％的压缩比进行三次冷轧; 并在440至650℃下进行最终真空退火7至9小时。
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